POWER REACTOR PROGRAM. Progress Report to E.I. du Pont de Nemours and Company for the Period June 24 Through July 19, 1957
Technical Report
·
OSTI ID:4327513
Progress in the development of Zircaloy clad uranium tanbular fuel elements is briefiy reviewed. Additional corrosion tests were made on defected Zircaloy-clad U-Zr alloy specimens to further establish the effects of Zr content on corrosion by water. Measurements were made of hydrogen diffusion through Al and Mg claddings on U and the subsequent swelling due to hydride formation. The permeability of FS1 magnesium (Al-Mg-Zn) to hydrogen was determined at 350 and 450 C. Values of S were 0.326 x 10/sup-4/ and 1.55 x 1O/sup -4/. (For preceding period see NMI-4350.) (D.E.B.)
- Research Organization:
- Nuclear Metals, Inc., Cambridge, Mass.
- NSA Number:
- NSA-13-001368
- OSTI ID:
- 4327513
- Report Number(s):
- NMI-4351
- Country of Publication:
- United States
- Language:
- English
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